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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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NN Asks: What did you learn from ANS’s Nuclear 101?
Mike Harkin
When ANS first announced its new Nuclear 101 certificate course, I was excited. This felt like a course tailor-made for me, a transplant into the commercial nuclear world. I enrolled for the inaugural session held in November 2024, knowing it was going to be hard (this is nuclear power, of course)—but I had been working on ramping up my knowledge base for the past year, through both my employer and at a local college.
The course was a fast-and-furious roller-coaster ride through all the key components of the nuclear power industry, in one highly challenging week. In fact, the challenges the students experienced caught even the instructors by surprise. Thankfully, the shared intellectual stretch we students all felt helped us band together to push through to the end.
We were all impressed with the quality of the instructors, who are some of the top experts in the field. We appreciated not only their knowledge base but their support whenever someone struggled to understand a concept.
John J. Volpe, George G. Smith, Daniel Klein, F. S. Frantz, Jocelyn C. Andrews
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 360-370
Technical Paper | doi.org/10.13182/NSE59-A25611
Articles are hosted by Taylor and Francis Online.
An experimental and analytical study of the flux distribution of two-region core configurations has been made for the TRX facility. The purpose of this study was to obtain an estimate of the sizes of critical configurations that would yield the same values of the basic reactor parameters in the inner region as a critical core consisting entirely of the inner region material and geometry. Several two-region cores have been constructed and experimental measurements of thermal utilization, resonance escape probability, and fast fission effects have been performed. Slow and fast neutron activation distributions have also been obtained. Two inner regions were constructed utilizing 1.3 w/o enriched UO2 fuel 0.384 in. in diameter and with a density of 10.53 gm/cm3. A third inner region utilized 1.3 w/o enriched uranium metal fuel with a diameter of 0.387 in. Light water served as the moderator and reflector in all cases. The experimental and theoretical results indicate that by utilizing two-region cores, measurements of microscopic parameters can be made for a wide variety of fuel sizes, fuel enrichments, and water-to-uranium volume ratios without the construction of full critical cores for each combination.
